Event Notification Report for April 05, 2007

AUTOMATIC REACTOR TRIP CAUSED BY SPURIOUS SAFETY INJECTION DURING TESTING

"At 09:08 am on 4/5/2007, during surveillance testing of Unit 2 Train A safeguards logic at power, a spurious Train A safety Injection (SI) actuation occurred resulting in reactor protection system (RPS) actuation. Train A SI was in "Test" at the time and should not have caused the RPS trip. The operating crew manually actuated Train B SI as required by emergency operating procedures. All automatic actions for a reactor trip and safety Injection occurred as required. Reactor Coolant System (RCS) pressure decreased below the shutoff head of the high head Emergency Core Cooling System (ECCS) pumps during the transient, resulting in momentary ECCS discharge to the RCS. SI has been terminated per emergency operating procedures.

"Prairie Island Unit 2 has been stabilized in mode 3, at about 2235 psig and 547 degrees average RCS temperature. Decay heat Is currently being removed by auxiliary feedwater and secondary steam dump to the main condenser. The cause of the actuation signal is under investigation. All control rods fully inserted. No primary power operated relief valves or safety valves lifted. No steam generator safeties lifted. Safeguards buses are powered by offsite power. The Unit 2 Emergency Diesel Generators (EDG) started but did not load.

"Unit 1 Control Rod Drive Mechanism cooling isolated as designed in response to the actuation and has since been restored. Otherwise, Unit 1 was unaffected and remains in mode 1 at 100% power."

The licensee notified the NRC Resident Inspector. The licensee will also be notifying the State, local and other Government agencies and will be issuing a press release.

OFFSITE NOTIFICATION - ALERT DECLARED DUE TO REPORT OF A FIRE IN THE CONTROL BUILDING

"At 1023 on April 5, 2007, an ALERT was declared because of a control room alarm and local report of a fire at transformer XPN08A. There was a possibility of affecting safety related equipment. Investigation at the scene did not reveal evidence of an active fire. Smoke and a red glow in the back of the transformer was observed. The transformer has been isolated from the bus and power supply.

"There was no evidence of equipment damage other than to the affected transformer. Areas adjacent to the transformer room were checked for fire, with no evidence of fire. The ALERT was closed out at approximately 1115.

"The NRC Resident Inspector was informed. State, local and other government agencies were informed of the event declaration. A press release was issued.


"NOTE: initial notification of the ALERT was made to the NRC (HOO) at 1040 CDT. (See EN43279)"

POTENTIALLY CONTAMINATED PERSON WITH A BACK INJURY TRANSPORTED TO LAKE EAST HOSPITAL

"At 2005, an injury occurred to a worker when the individual fell and injured his back. At 2122, the worker was attended by local Emergency Medical Personnel who transported the individual to our local Hospital. Due to his back injury his back will not be able to be completely monitored until arrival to the hospital. The individual is being classified as potentially contaminated. Radiation [Protection] personnel are accompanying the victim on the ambulance and to the local hospital emergency room to aid in radiological assessment.

"Due to our procedures we will be making notifications to the State Of Ohio and the local county Emergency Management Agencies of the incident. Due to the offsite notifications a 4 hour non-emergency call is required."

The individual was a contractor onsite for outage support.

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 2249 ON 4/5/07 FROM A. RABENOLD TO SNYDER * * *

"The contractor individual was found in the Containment Drywell 630 foot elevation. He fell off of scaffolding approximately 4-5 feet to the grating. When the medical personnel arrived at the scene they found him unconscious. He regained [consciousness] when medical personnel arrived at the scene.

"At 2218 [the licensee received a] report from Radiation Protection personnel that the individual was not contaminated."

Notified R3DO (L. Kozak).


* * * Update on 04/06/07 at 1130 EDT from M. Nemcek to MacKinnon * * *

The injured person was found not to have contamination on him but it was reported to Perry Nuclear Power plant that fixed contamination was found on his Protective Clothing (PC), Safety Belt and Tool Belt. Fixed contamination on the PC direct contact reading was between 100 to 150 cpm. Fixed direct on contact contamination on the Safety Belt & the Toll Belt was between 100 to 500 cpm. No contamination found in the ambulance or in the Hospital. NRC Resident Inspector was left a message of this information by the licensee. NRC R3DO (L. Kozak) notified.

ILLINOIS AGREEMENT STATE REPORT

Pinnacle Food Group located in St. Elmo, IL reported that between March 13 through 20, 2007 they were performing general maintenance for the up coming canning season. After the cleanup they discovered that a Industrial Dynamics Model FT50 fixed gauge containing 100 millicuries of Am-241 used for fill level measurements was taken as scrap metal to either Grossman Iron & Steel or PSE Metals which are both located in St. Louis, MO. These scrap metal yards were both notified on 04/05/07 by Pinnacle Food Group that their scrap yard may have the missing gauge in their yard. Pinnacle Food Group has hired a consultant and he arrived at the scrap yards on 04/06/07 and he is looking for the missing gauge. So far no contamination has been detected in either scrap yard.

IL. Incident # IL-070020.

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.

ALERT DECLARED DUE TO A FIRE IN THE CONTROL BULDING

At 1023 Central Daylight Time the licensee declared an Alert due to a transformer fire in the non-safety related PN08 transformer phase 'A.' There were no visible flames seen by onsite licensee personnel but an area of the transformer was glowing with a smokey haze in the area. The fire brigade responded.

The plant was already in a shut down condition entered on 4/1/07 for a refueling outage. Decay heat was being removed using Residual Heat Removal the train 'B.' The licensee declared the alert based on a potential impact to the operating Residual Heat Removal train.

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1215 ON 4/5/07 FROM LICENSEE COMMUNICATOR TO SNYDER * * *

The licensee exited the Alert condition at 1215 Eastern Daylight Time based on their assessment that no impact to operating safety related RHR equipment occurred and any impact would have been conservative in that flow to the core would not have been interrupted.

The licensee notified the NRC Resident Inspector.